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Technical Paper

A New Approach for Assessing the Required Tritium Breeding Ratio and Startup Inventory in Future Fusion Reactors

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Pages 309-353 | Published online: 09 May 2017

REFERENCES

  • M. A. ABDOU, E. L. VOLD, C. Y. GUNG, M. Z. YOUSSEF, and K. SHIN, “Deuterium-Tritium Fuel Self Sufficiency in Fusion Reactors,” Fusion Technol., 9, 250 (1986).
  • W. F. VOGELSANG, “Breeding Ratio, Inventory, and Doubling Time in a D-T Fusion Reactor,” Nucl. Technol., 15, 470 (1972).
  • F. CARRÉ, E. PROUST, and A. ROCABOY, “Analysis of the Tritium Requirements for a Power Reactor,” Nucl. Technol./Fusion, 4, 2 Part 2, 93 (1983).
  • J. JUNG, “An Assessment of Tritium Breeding Requirements Based on the Tritium Fuel Cycle,” Fusion Technol., 9, 308 (1986).
  • Y. ASAOKA, K. OKANO, T. YOSHIDA, and K. TOMA-BECHI, “Requirements of Tritium Breeding Ratio for Early Fusion Power Reactors,” Fusion Technol., 30, 3 Part 2A, 853 (1996).
  • W. KUAN, M. A. ABDOU, and R. S. WILLMS, “Time-Dependent Tritium Inventories and Flow Rates in Fuel Cycle Components of a Tokamak Fusion Reactor,” Fusion Eng. Des., 28, 329 (1995).
  • W. KUAN, R. S. WILLMS, and M. A. ABDOU, “Dynamic Simulation of a Proposed ITER Tritium Processing System,” Fusion Technol., 28, 3 Part 1, 664 (1995).
  • W. KUAN and M. A. ABDOU, “An Investigation of Plasma-Facing Component Material Effects on Tritium Reprocessing Systems,” Fusion Technol., 28, 3 Part 1, 658 (1995).
  • W. KUAN and S. K. HO, “Simplified Fuel Cycle Tritium Inventory Model for Systems Studies—An Illustrative Example with an Optimized Cryopump Exhaust System,” Proc. 16th IEEE/NPSS Symp. Fusion Engineering, Champaign, Illinois, September 30–October 5, 1995.
  • A. BUSIGIN and P. GIERSZEWSKI, “CFTSIM-ITER Dynamic Fuel Cycle Model,” Int. Symp. Fusion Nuclear Technology 4, Tokyo, Japan, 1997, Fusion Eng. Des. (in press).
  • A. BUSIGIN and S. K. SOOD, “Steady State and Dynamic Simulation of the ITER Hydrogen Isotope Separation System,” Fusion Technol., 28, 3 Part 1, 544 (1995).
  • G. R. LONGHURST, R. A. ANDERL, T. J. DOLAN, and M. J. MULOCK, “Modeling Tritium Processes in Plasma-Facing Beryllium,” Fusion Technol., 28, 3 Part 1, 1217 (1995).
  • J. N. BROOKS, R. CAUSEY, G. FEDERICI, and D. N. RUZIC, “Assessment of Erosion and Surface Tritium Inventory Issues for the ITER Divertor,” J. Nucl. Mater., 241–243, 294 (1997).
  • G. FEDERICI, A. R. RAFFRAY, M. C. BILLONE, C. H. WU, S. CHO, and M. A. ABDOU, “An Assessment of Models for Tritium Release from Ceramic Breeders for Blanket Analysis Applications,” J. Nucl. Mater., 212–215, 1003 (1994).
  • A. R. RAFFRAY, M. C. BILLONE, G. FEDERICI, and S. TANAKA, “Progress in Tritium Retention and Release Modeling for Ceramic Breeders,” Fusion Eng. Des., 28, 240 (1995).
  • M. C. BILLONE, “TIARA Analysis of Tritium Inventory in Li2O,” Fusion Eng. Des., 28, 313 (1995).
  • S. SHIMAKAWA et al., “Estimation of the Tritium Production and Inventory in Beryllium,” Fusion Eng. Des., 28, 215 (1995).
  • G. FEDERICI, D. HOLLAND, G. JANESCHITZ, and C. H. WU, “The Influence of Key Operation Parameters and Material Properties on the Quantification of Tritium Inventory and Permeation in the Plasma Facing Components of ITER,” J. Nucl. Mater., 241–243, 260 (1997).
  • G. FEDERICI et al., “Tritium Inventory in the ITER PFC’s: Predictions, Uncertainties, R&D Status and Priority Needs,” Int. Symp. Fusion Nuclear Technology 4, Tokyo, Japan, 1997, Fusion Eng. Des. ( in press).
  • W. KUAN, G. FEDERICI, P. GIERSZEWSKI, and M. SUGIHARA, “A Simplified Torus Module for Use Within an Integrated Dynamic Fusion Fuel Cycle Tritium Model for ITER,” Proc. 17th IEEE/NPSS Symp. Fusion Engineering, San Diego, California, October 6–10, 1997.
  • P. GIERSZEWSKI, “Tritium Supply for Near-Term Fusion Devices,” Fusion Eng. Des., 10, 399 (1989).
  • L. J. WITTENBERG, “Comparison of Tritium Production Reactors,” Fusion Technol., 19, 3, Part 2a, 1040 (1991).
  • L. J. WITTENBERG, “The Cost of Tritium Production in a Fusion Reactor,” Fusion Technol., 21, 2, Part 2, 886 (1992).
  • W. M. STACEY et al., “ATokamak Tritium Production Reactor,” Fusion Technol., 32, 563 (1997).
  • H. SCHNAUDER, C. NARDI, and M. EID, “Comparative Availability Analysis of the Four European DEMO Blanket Concepts in View of the Selection Exercise,” Fusion Eng. Des., 36, 343 (1997).
  • L. A. EL-GUEBALY and the ARIES TEAM, “Breeding Potential of Candidate Breeders for the U.S. Demo Power Plant,” Proc. 16th IEEE/NPSS Symp. Fusion Engineering, Champaign, Illinois, September 30–October 5, 1995, p. 1198 Institute of Electrical and Electronics Engineers (1995).
  • K. NAKAHARA, Y. SEKI, and S. KOBAYASHI, “Thermal Effect of Periodical Bakeout on Tritium Inventory in First Wall and Permeation to Coolant in Reactor Life,” Fusion Eng. Des., 10, 385 (1989).
  • F. NAJMABADI et al., “The ARIES-I Tokamak Reactor Study,” UCLA-PPG-1323, Vol. II, University of California, Los Angeles (1991).
  • L. A. EL-GUEBALY and the ARIES TEAM, “Overview ofARIES-RS Neutronics and Radiation Shielding: Key Issues and Main Conclusions,” Fusion Eng. Des., 38, 139 (1997).
  • R. W. MOIR et al., “HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design,” Fusion Technol., 25, 5 (1994).
  • M. A. ABDOU et al., “Critical Technical Issues and Evaluation and Comparison Studies for Inertial Fusion Energy Reactors,” Fusion Eng. Des., 23, 251 (1993).
  • L. J. PERKINS, “Complexity and Availability for Fusion Power Plants: The Potential Advantages of Inertial Fusion Energy,” J. Fusion Energy, 16/4, 307 (1997).
  • R. W. MOIR, “Liquid First Walls for Magnetic Fusion Energy Configurations,” Nucl. Fusion, 37/4, 557 (1997).
  • M. A. ABDOU, “A Volumetric Neutron Source for Fusion Nuclear Technology Testing and Development,” Fusion Eng. Des., 27, 111 (1995).
  • S. P. WALKER and M. G. HAINES, “An Assessment of the Prospects for Economic D-T Tokamak Fusion,” Fusion Eng. Des., 36, 387 (1997).

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